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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 307.02-SQN SPECIAL PROGRAM REPORT TYPE: Sequoyah Nuclear Plant - Element REVISION NUMBER: 2 TITLE: Handlin6 Safeguards Information REASON FOR REVISION:
Incorporata SRP, TAS conunents and SQN Corrective Action Response Revision 1 Incorporate SRP conunents Revision 2 PREP &MATION PREPARED BY:
R. E. Jones //-@fd SIGNATURE DATE l
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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EMPLOYEE CONCERNS TASK GROUP OPERATIONS CEG Subcategory: Nuclear Power Site Programs and Procedures Element: Handling of Safeguards Information Report Number: 307.02-SQN Revision 2 11-85-018-001 IN-85-915-003 Evaluator: R. E. Jones 10/13/86 R. E. Jones Date Reviewed by: (( ops C
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Revision 2 I. IMPROPER STORAGE AND CONTROL OF SAFEGUARDS INFORMATION The concerns expressed in this report are (1) Sequoyah Nuclear Plant (SQN) specific item dealing with safeguards material being improperly stored and controlled and (2) an employee concern considered generic to SQN that addressed lots of safeguards information.
II. SPECIFIC EVALUATION METHODOLOGY This evaluation addresses two concerns.
The employee concerns identified to Quality Technology Company (QTC) are i
as follows:
A. II-85-018-001 " Safeguards information at the Sequoyah Nuclear l Power Plant is being kept in uncontrolled books and l
not secured as per TVA policy and/or NRC guidelines."
B. IN-85-915-003 "A safeguards drawing (45 W 39-4 Revision 10) was lost. An investigation into this lost document stated it was destroyed. There is no objective evidence to support this report."
Concern II-85-018-001 was closed by Nuclear Safety Review Staff (NSRS) investigation report I-85-135-WBN and evaluation of the concern for SQN is based on a review of the NSRS report and line management response to j the NSRS investigation. Evaluation of.this concern centered on the l validity of the employee concern, the adequacy of NSRS recommendations l to clo'se out the concern, a verification of the line management response to NSRS recommendations, and a review and verification of the corrective actions that resulted from the investigation.
Concern IN-85-915-003 was considered as generic to SQN based on the results of an NSRS investigation I-85-459-WBN at Watts Bar and was evaluated at SQN as an open concern. The ECTG evaluation at SQN was based on the associated NSRS report recommendations and the line management responses to the report. Appropriate procedures at SQN were reviewed to determine the adequacy of the site procedures and interviews were conducted to verify that the program is being properly implemented.
III. FINDINGS Improperly Stored Safeguards Material (Concern 11-85-018-001)
NSRS investigation report number I-85-135-WBN substantiated the concern of improperly stored and controlled safeguards material at SQN. The investigating team (composed of NSRS, Public Safety Service (PSS), and Quality Technology Company (QTC) personnel) found safeguards documents in a locked PSS office which were not protected or accounted for in a manner that met Nuclear Regulatory Control (NRC) regulations and TVA policy / procedures. ,
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Revision 2 As a result of the investigation the following NSRS recommended actions were taken by line managemant:
(1) The safeguards material was immediately transported to a proper storage area before departure of the investigating team; and (2) the Sequoyah Public Safety Service issued Security Degradation / Incident Report Number 85-051-06 and accounted for all safeguards documents. The NSRS investigation determined that the improperly stored documents had not been compromised and SQN PSS subsequently reinstructed all members of the security force on their individual responsibilities involving the safe handling and storage of safeguards material. This action is documented in a memorandum dated September 5, 1985 (reference 2).
Lost Safeguards Drawing (Concern IN-85-915-003)
Title 10 CFR 73 and NUREG-0794 establishes the requirements for the
- protection of safeguards information. Evaluation of SQN procedures 0401.01 (reference 5), AI-25, part I (reference 7), AI-25, part II (reference 8), and Standard Practice SQA-132 (reference 6) determined that the regulatory requirements are adequately incorporated into the SQN program. Further, evaluator interviews with SQN Security and Document Control personnel confirmed that these personnel have sufficient knowledge of these procedures to implement the program.
NSRS investigation report I-85-459-WBN, which was written to address the problem originally at WBN, included a recommendation to revise the Document Control Safeguards Document Log to include a reference to the drawing revision and unit applicability as additional information to i provide additianal controls for traceability beyond that of the drawing ,
l number. A review of the Safeguards Log at SQN determined that this NSRS recommendation is also applicable to SQN and at present has not been implemented.
Conclusion NSRS Report I-85-135-WBN adequately addressed concern XX-85-018-001.
Line management's response was adequate and corrected the deficiencies found during the investigation.
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Revision 2 Employee Concern XX-85-018-001 was substantiated at SQN. However, adequate corrective action was immediately implemented and resolved the specific concern.
Employee Concern IN-85-915-003 was not substantiated at SQN. A review of SQN safeguards information procedures identified no programmatic deficiencies. However, this evaluation concurs with the NSRS recommendation made at Watts Bar that the Document Control Safeguards Document Log should be revised to include the drawing revision number and unit applicability number on the form. At present, the form used at SQN does not utilize these identifiers.
The concerns addressed in this report have no safety significance at SQN.
IV. ROOT CAUSE Personnel error in not following procedures.
V. GENgEIC APPLICABILITY Employee Concern 11-85-018-001 is not generically applicable to other TVA plant sites. Based on the findings of this report, SQN safeguards procedures adequately address regulatory requirements for the protection of safeguards information. The incident addressed during this evaluation was not the result o.f programmatic deficiencies but was an isolated occurrence of personnel r.ot following procedures.
Employee Concern IN-85-915-003 remains generically applicable to BFN because an adequate evaluation of the BFN Safeguards Information Program has not been conducted to determine adequacy.
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Revision 2 VI. REFERENCES
- 1. NSRS Investigation Report Number I-85-135-WBN, " Safeguards Information (SQN)"
- 2. Nemorandum from John S. Rozek to K. W. Whitt dated September 5, 1985, "NSRS Investigation Report Number I-35-135-WBN"
- 3. Code of Federal Regulations, 10 CFR 73
- 4. NUREG-0794, " Protection of Unclassified Safeguards Information"
- 5. SQN Procedure 0401.01, " Protection of Safeguards Information Within the Division of Nuclear Power"
- 6. SQN Standard Practice SQA-132, " Safeguards Information Program"
- 7. SQN Administrative Instruction AI-25 (Part I), " Drawing Control After Licensing"
- 8. SQN Administrative Instruction AI-25 (Part II), " Revision of As-Constructed Drawings"
- 9. NSRS Investigation Report I-85-459-WBN, " Safeguards Drawing Incident" VII. IlgtEDIATE OR LONG-TERN CORRECTIVE ACTION SQN's response to 307.02-SQN Revision 0 is as follows IR2 (CATD_30702-SQN-01): l A. I-85-459-WBN Safeguards Document Log Revision Required The Safeguards Document Log now utilized by the DCU should be changed to include revision and unit applicable notations.
Action "The Sequoyah Safeguard Document Log was immediately revised upon notification of recommendation to include revision and applicable unit (s)."
B. I-85-459-WBN Guidance for Safeguards Incideat Investigetion l
The involved line organizations should seek clarification and guidance in regard to implementation of safeguards incident investigations and disposition. That clarification and guidance received should be translated into working level instructions and training.
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Revision 2 Action
" Office of Nuclear Power at Sequoyah Standard Practice SQA-132 Safeguards Information Program adequately addresses the handling of safeguards information. Training was conducted at Sequoyah on July 11, 1986 - September 12, 1986 for personnel handlingsafeguard information (see attached). Management at Sequoyah is to ensure their personnel are aware and adhere to safeguard requirements."
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PAGE REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY RUN TIME 'II:4 OFFICE OF NUCLEAR P0HER RUN DATE - 10/2 FREQUENCY - REQUEST EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS) .
g ONP - 1555 - RHM LIST OF EMPLOYEE CONCERN INFORMATION -
SUBCATEGORY: 30702 HANDLING OF SAFEGUARDS INFORMATION CATEGORY: OP PLANT OPER. SUPPORT KEYHORD A l S GENERIC KEYHORD B g H APPL QTC/NSRS P S CONCERN KEYHORD C CONCERN SUB R PLT BBSH INVESTIGATION R DESCRIPTION KEYHORD D NUMBER CAT CAT D LOC FLQB REPORT A SAFE-GUARDS DRAHING (45H39-4 REV 1 FALSIFICATION I IH 00000 S HBN NNYN I-85-459-HBN 0) HAS LOST. AN INVESTIGATION INTO DOCUMENT STATUS IN 915-003 30702 REPORT CONSTRUCTION T50133 OP THIS LOST DOCUMENT STATED IT HAS DES f GENERAL TROYED. THERE IS NO OBJECTIVE EVIDE y NCE TO SUPPORT THIS REPORT. (ADDITI ONAL FACTS / NAMES ARE KNDHN, HITHELD DUE TO CONFIDENTIALITY). CI HAS NO FURTHER INFORMATION.
D SS SAFEGUARDS INFORMATI0H AT THE SEQUAY POWER XX 018-001 OP 30702 N SQN NNNN AH NUCLEAR P0HER PLANT IS BEING KEPT SECURITY K-FORM OPERATIONS T50022 IN UNCONTROLLED BOOKS AND NOT SECUR SECURITY g ED AS PER TVA POLICY AND/OR NRC GUID ELINES (LOCATIONS, INDIVIDUALS KNOHN
)
2 CONCERNS FOR CATEGORY OP SUBCATEGORY 30702 9
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